ML20135F202
| ML20135F202 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/06/1996 |
| From: | Trimble D NRC (Affiliation Not Assigned) |
| To: | Campbell W CAROLINA POWER & LIGHT CO. |
| References | |
| IEB-96-002, IEB-96-2, TAC-M95562, TAC-M95563, NUDOCS 9612120436 | |
| Download: ML20135F202 (3) | |
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UNITED STATES p-j
,j NUCLEAR REGULATORY COMMISSION
't WASHINGTON. D.C. 20066-0001 i
l k..<,o8 December 06, 1996 l
l Mr. W. R. Campbell, Vice President Carolina Power & Light Company Brunswick Steam Electric Plant Post Office Box 10429 Southport, North Carolina 28461
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RELATED TO BULLETIN 96-02, l
" MOVEMENT OF HEAVY LOADS OVER SPENT FUEL, OVER FUEL IN THE REACTOR l
CORE, OR OVER SAFETY-RELATED EQUIPMENT" - BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 & 2 (TAC N0s. M95562 AND M95563)
Dear Mr. Campbell:
The NRC staff has evaluated the responses to Bulletin 96-02, " Movement of Heavy Loads over Spent Fuel, Over Fuel in the Reactor Core, or over Safety-Related Equipment," and found that some licensees without single-failure-proof cranes have analyzed or are planning to analyze postulated spent fuel storage cask and transportation cask drop accidents to establish design basis accidents for their facilities.
l Typical cask drop analyses for in-plant cask movement have addressed the effects of a drop on plant equipment and/or cask integrity. Those analyses have assumed that the cask was in its final condition with its structural lids bolted or welded in place and that the fuel remained in the cask at all times, though the integrity of the cask might be breached during the cask drop.
However, since most cask lids are not secured until after the casks are removed from the pool, it is conceivable that a cask could drop in a tipped-over orientation. The cask could be also dropped back into the spent fuel pool or adjacent area, possibly dislodging the cask lid or dislodging the cask lid and ejecting some or all the spent fuel elements onto the top of the spent fuel racks, the floor of the pool, or adjacent areas.
This accident scenario involves the potential for dropping the cask during movement from the spent fuel pool to the area within the plant building where 1
activities such as drying, inerting, and final securing of the cask lid are completed. Offsite dose effects are not expected from a cask drop and tip-over event in which there is a loss of both the cask lid and fuel confinement.
l However, the effect of such an event on the operation of the facility needs to l
be assessed.
For example, evaluations may need to determine if any vital l
plant areas are rendered inaccessible and if operations or maintenance kd activities would be significantly hampered. Such evaluations would involve, but are not limited to, the cask and crane designs, the load paths, and the i
extent to which the licensee can demonstrate its capability of performing GU\\
actions necessary for safe shutdown with resulting plant damage and in the
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presence of a radiological source term.
To support further NRC staff evaluation of this potential cask drop scenario while the reactor is at power (in all modes other than cold shutdown, refueling, and defueled), please provide the following:
I 9612120436 961206 PDR ADOCK 05000324 12Y062 NRC FILE CENTER COPY
1.
An evaluation of your crane design, load path, and cask loading and unloading processes that supports a determination that the scenario described above is not credible at your facility, or 2.
If you determine that the event is credible, please provide the following:
(a)
An analysis of a possible drop of a spent fuel storage or transportation cask involving a drop that results in the tipping over of the spent fuel cask, loss of the cask lid, or loss of the cask lid and ejection of the spent fuel from the cask into the spent fuel pool or areas adjacent to the pool. This load drop / consequence analysis should include a dose analysis to personnel involved in the cask movement for the time immediately following the accident.
Also, the analysis should address personnel exposure resulting from required entry into, plant areas affected by the event and the impact of elevated dose fields on the ability to reach safe shutdown or continue normal' plant operation.
(b)
An evaluation addressing the potential for criticality resulting from the postulated cask drop accident scenario described above.
(c)
An evaluation. that addresses possible means of recovering from the postulated cask drop accident scenario described above.
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(d)
An evaluation that addresses whether the potential impact of the scenario described above on othe~r parts 'of the facility (e.g., the spent fuel pool) is bounded by.previ,ous load drop analyses.
This letter contains information collections that are subject to the Paperwork Reduction Act-of 1995'(44 U.S.C. 3501 et seq.). These information collections were approved by 'the Office of Management and Budget, approval number 3150-0012, which expires June,30,~1997. The public reporting burden for this collection of information is covered by the original estimate of 600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> per response for responding to Bulletin 96-02.
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Please provide your response within 60 days of your receipt of this request for information.
If you need clarification of the staff's request, please contact me at (301) 415-2019.
Sincerely, (Original Signed By) 4 David C. Trimble, Project Manager Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324 DISTRIBUTION:
PUBLIC PD II-1/ RF cc:
See next page DOCUMENT NAME: G:\\BRUNSWIC\\BR95562.LTR Docket. File Pray /
OFFICE PM:PDII-l LA:PDII-l SPLB*
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NAME DTrimb1N Dunning [ok TMarsh MRejdar't i
DATE 12/6/96 12/5/96 12/02/96 1[/ h /96 k gis)No Yes/No Yes/No h COPY (Ves/No s
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OFFICIAL RECORD COPY
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Mr. W. R. Campbell Brunswick Steam Electric Plant Carolina Power & Light Company Units 1 and 2 cc:
Mr. William D. Johnson Ms. Karen E. Long
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Vice President and Senior Counsel Assistant Attorney General l
Carolina Power & Light Company State of North Carolina Post Office Box 1551 Post Office Box 629 l
Raleigh, North Carolina 27602 Raleigh, North Carolina 27602 Mr. Jerry W. Jones, Chairman Mr. Robert P. Gruber Brunswick County Board of Comissioners Executive Director Post Office Box 249 Public Staff - NCUC Bolivia, North Carolina 28422 Post Office Box 29520 Raleigh, North Carolina 27626-0520 Resident Inspector U.S. Nuclear Regulatory Comission Mr. W. Levis 8470 River Road Director Southport, North Carolina 28461 Site Operations l
Brunswick Steam Electric Plant Regional Administrator, Region II Post Office Box 10429 U.S. Nuclear Regulatory Comission Southport, North Carolina 28461 101 Marietta St., N.W., Ste. 2900 Atlanta, Georgia 30323 Mr. William H. Crowe, Mayor City of Southport Mr. Dayne H. Brown, Director 201 East Moore Street Division of Radiation Protection Southport,. North Carolina 28461 N.C. Department of Environmental, Commerce and Natural Resources Mr. Dan E. Sumers Post Office Box 27687 Emergency Management Coordinator Raleigh, North Carolina 27611-7687 New Hanover County Department of Emergency Management Mr. R. P. Lopriore Post Office Box 1525 Plant Manager Wilmington, North Carolina 28402 Carolina Power & Light Company Brunswick Steam Electric Plant Mr. J. Cowan Post Office Box 10429 Vice President Southport, North Carolina 28461 Nuclear Services and Environmental Support Department Public Service Comission Carolina Power & Light Company State of South Carolina Post Office Box 1551 - Mail OHS 7 Post Office Drawer 11649 Raleigh, North Carolina 27602 Columbia, South Carolina 29211 Mr. Gerald D. Hicks Mr. Milton Shymlock Manager - Regulatory Affairs U. S. Nuclear Regulatory Comission Carolina Power & Light Company 101 Marietta Street, N.W. Suite 2900 Post Office Box 10429 Atlanta, Georgia 30323-0199 Southport, North Carolina 28461 i
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